Graphite core components which form the moderator and reflector structures in High Temperature Reactor Pebble bed Module (HTR-PM) are subjected to various kinds of loads. Graphite keys and dowels are designed to maintain the structure integration and dimension stability of the graphite assembly during the operation of the plant. The dowel-brick structures bear the shear loads between different layers of the graphite bricks. Experiments have been carried out to study the shear load capacity of the graphite dowel and dowel-brick structure. The load-displacement curves and the failure modes were obtained for different dowels used in HTR-PM. The results show that for a dowel-brick structure subjected to lateral load, graphite brick failed first with cracks initiated around the dowel socket. The load capacity of the dowel-brick structure is lower than that of the dowel itself. The shear stiffness of the dowel-brick structure was obtained to calculate the relative displacement of adjacent graphite bricks connected by dowels.
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2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference
July 30–August 3, 2012
Anaheim, California, USA
Conference Sponsors:
- Nuclear Engineering Division
- Power Division
ISBN:
978-0-7918-4496-0
PROCEEDINGS PAPER
Graphite Component Testing on the Load Capacity of the Dowel-Brick Structure in HTR-PM
Zonggang Wang,
Zonggang Wang
Tsinghua University, Beijing, China
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Zhensheng Zhang
Zhensheng Zhang
Tsinghua University, Beijing, China
Search for other works by this author on:
Li Shi
Tsinghua University, Beijing, China
Libin Sun
Tsinghua University, Beijing, China
Zonggang Wang
Tsinghua University, Beijing, China
Yuqin Hu
Tsinghua University, Beijing, China
Zhensheng Zhang
Tsinghua University, Beijing, China
Paper No:
ICONE20-POWER2012-54945, pp. 157-163; 7 pages
Published Online:
October 30, 2013
Citation
Shi, L, Sun, L, Wang, Z, Hu, Y, & Zhang, Z. "Graphite Component Testing on the Load Capacity of the Dowel-Brick Structure in HTR-PM." Proceedings of the 2012 20th International Conference on Nuclear Engineering and the ASME 2012 Power Conference. Volume 2: Plant Systems, Structures, and Components; Safety and Security; Next Generation Systems; Heat Exchangers and Cooling Systems. Anaheim, California, USA. July 30–August 3, 2012. pp. 157-163. ASME. https://doi.org/10.1115/ICONE20-POWER2012-54945
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